• Nuclear Engineering and Technology
• /
• 제56권2호
• /
• pp.644-654
• /
• 2024

After the Tohoku earthquake and tsunami (Japan, 2011), regulatory efforts to mitigate external hazards have increased both the safety requirements and the total capital cost of nuclear power plants (NPPs). In these circumstances, identifying not only disaster robustness but also cost-effective capacity setting of NPPs has become one of the most important tasks for the nuclear power industry. A few studies have been performed to relocate the seismic capacity of NPPs, yet the effects of multiple hazards have not been accounted for in NPP capacity optimization. The major challenges in extending this problem to the multihazard dimension are (1) the high computational costs for both multihazard risk quantification and system-level optimization and (2) the lack of capital cost databases of NPPs. To resolve these issues, this paper proposes an effective method that identifies the optimal multihazard capacity of NPPs using a multi-objective genetic algorithm and the two-stage direct quantification of fault trees using Monte Carlo simulation method, called the two-stage DQFM. Also, a capacity-based indirect capital cost measure is proposed. Such a proposed method enables NPP to achieve safety and cost-effectiveness against multi-hazard simultaneously within the computationally efficient platform. The proposed multihazard capacity optimization framework is demonstrated and tested with an earthquake-tsunami example.

• 대한인간공학회지
• /
• 제23권2호
• /
• pp.13-24
• /
• 2004

Human error has brought about accidents more than 50% in system of a large size and complicated expecially in nuclear power plants(NPPs). The technology of Man Machine Interface(MMI) has been changed to the digitalized controls employing computer-based technology. According to this trend. the human factors guidelines are becoming main issue for reliable supports to digitalized information displays. However. the existing human factors guidelines is not enough for advanced information display on NPPs. The purpose of this research is to develop the reliable design and evaluation guidelines for advanced information display in main control room (MCR) of NPPs. In this study. the various general human factors guidelines concerning information display on CRT are integrated on data base management system. unified based on the integration rules. and applied in computer based procedures. The use of the integrated guidelines are expected to evaluate the existing information display on MCR in NPPs from the human factors point of view.

• Corrosion Science and Technology
• /
• 제14권6호
• /
• pp.325-330
• /
• 2015

Pipe wall-thinning by flow-accelerated corrosion (FAC) is a significant and costly damage of secondary system piping in nuclear power plants (NPPs). All NPPs have their management programs to ensure pipe integrity from wall-thinning. This study analyzed the pipe wall-thinning caused by changing the amine, which is used for adjusting the water chemistry in the secondary system of NPPs. The pH change was analyzed according to the addition of amine. Then, the wear rate calculated in two different amines was compared at the steam cycle in NPPs. As a result, increasing the pH at operating temperature (Hot pH) can reduce the rate of FAC damage significantly. Wall-thinning is affected by amine characteristics depending on temperature and quality of water.

• Corrosion Science and Technology
• /
• 제11권4호
• /
• pp.129-134
• /
• 2012

UT(Ultrasonic Test), one of the non-destructive tests, is the most common thickness measurement method for evaluating the wear rate in NPPs(Nuclear Power Plants). UT is used widely because it is easy and safe for use. However some amount of error inevitably occurs in attempting to measure the thickness. The error, that could make the thickness data thicker or thinner, may affect estimation of wear rate in pipes. NPPs are composed of a lot of pipes and components. Some of them are tested to check the current status during RFO(Re-Fueling Outage). Reliability analysis of UT is essential for evaluating pipe wear rate and establishing the long-term management plan in NPPs. This paper reviewed the cause of error occurrence and presented the UT data reliability analysis method. Also, this paper shows the application result of reliability analysis to the UT data acquired in NPPs.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1997년도 추계학술발표회논문집(1)
• /
• pp.443-448
• /
• 1997

The intelligent software system for nuclear power plants (NPPs) has been conceptually designed in this study. Its design goals are to operate NPPs in n improved manner and to support operators' cognitive tasks. It consists of six major modules such as "Information Processing," "Alarm Processing," "Procedure Tracking," "Performance Diagnosis," and "Event Diagnosis" modules for operators and "Malfunction Diagnosis" module for maintenance personnel. Most of the modules have been developed for several years and the others are under development. After the completion of development, they will be combined into one system that would be main parts of advanced control rooms in NPPs. that would be main parts of advanced control rooms in NPPs.

• 한국안전학회지
• /
• 제14권1호
• /
• pp.177-184
• /
• 1999

PSA(Probabilistic Safety Assessment) methodology is widely used on assessing the safety of Nuclear Power Plants(NPPs) quantitatively in the domestic nuclear field. Initiating event frequencies are absolutely needed to conduct PSA, and they considerably affect PSA results. There is no domestic database where domestic trip event cases are reflected, so they are used to assess the safety of NPPs that are from the foreign database. In this paper, operating experience data from the Korean NPPs was collected and analyzed for the trip event cases, which are necessary to determine the initiating events and their frequencies. Korean NPPs have experienced five of 16 initiating events, which we LOFW. LOCV, LOCCW, LOOP and GTRN as a result of analyzing the trip event cases. Initiating frequencies based on the domestic trip event cases are analyzed, and they are similar to that from the foreign database.

• 한국전자통신학회논문지
• /
• 제12권5호
• /
• pp.725-730
• /
• 2017

원전의 안전 유지를 위한 계측제어계통에 일반적인 IT 자원을 활용하는 사례가 증가하고 있다. 이에 따라 기존 IT 자원이 갖는 잠정적인 보안 취약점으로 인해 원전 사이버 보안 침해 사고가 발생할 수 있으며, 원전의 가동 중단뿐만 아니라 국가적 재난에 이르는 심각한 사고를 야기할 수 있다는 문제가 제기되고 있다. 국내 원자력 규제기관에서는 이에 대응하기 위해 원전 사이버 보안 규제지침을 개발하고 규제 대상 및 범위를 확대시키고 있지만, 원전의 일반적인 보안 문제뿐만 아니라 원전 취약점에 특화된 공격에도 대응할 수 있는 방안이 필요하다. 이에 본 논문에서는 R.G.5.71에서 규정하고 있는 내용 중 취약점 점검과 관련된 42개 항목을 선별하여 5가지의 유형으로 분류 분석하였다. 제안된 분석 내용을 바탕으로 취약점 점검 도구를 개발한다면 원전 사이버 보안 취약점 점검 효율성을 향상시킬 수 있을 것으로 판단된다.

• Nuclear Engineering and Technology
• /
• 제36권1호
• /
• pp.112-120
• /
• 2004

The purpose of this paper is to analyze the piping failure frequency for the main feedwater system in domestic nuclear power plants(NPPs) for the application to an in-service inspection(ISI), leak before break(LBB) concept, aging management program(AMP), and probabilistic safety analysis(PSA). First, a database was developed for piping failure events in domestic NPPs, and 23 domestic piping failure events were collected. Among the 23 events, 12 locations of wall thinning due to flow accelerated corrosion(FAC) were identified in the main feedwater system in 4 domestic WH 3-loop NPPs. Two types of the piping failure frequency such as the damage frequency and rupture frequency were considered in this study. The damage frequency was calculated from both the plant population data and damage(s) including crack, wall thinning, leak, and/or rupture, while the rupture frequency was estimated by using both the well-known Jeffreys method and a new method considering the degradation due to FAC. The results showed that the damage frequencies based on the number of the base metal piping susceptible to FAC ranged from $1.26{\times}10^{-3}/cr.yr\;to\;3.91{\times}10^{-3}/cr.yr$ for the main feedwater system of domestic WH 3-loop NPPs. The rupture frequencies obtained from the Jeffreys method for the main feedwater system were $1.01{\times}10^{-2}/cr.yr\;and\;4.54{\times}10^{-3}/cr.yr$ for the domestic WH 3-loop NPPs and all the other domestic PWR NPPs respectively, while those from the new method considering the degradation were higher than those from the Jeffreys method by about an order of one.

• 한국정보통신학회논문지
• /
• 제22권10호
• /
• pp.1392-1397
• /
• 2018

원자력 발전소는 주요 국가에서 관리하는 핵심 시설로 보호되고 있으며, 원자력 발전소의 설비들에 일반적인 IT 기술을 적용하여 기존에 설치된 아날로그 방식의 운용자원을 제외한 나머지 자산에 대해 디지털화된 자원을 활용하는 비중이 높아지고 있다. 네트워크를 사용하여 원전의 IT자산을 제어하는 것은 상당한 이점을 제공할 수 있지만 기존 IT자원이 지닌 잠정적인 보안 취약점(Vulnerability)으로 인해 원자력 시설 전반을 위협하는 중대한 사이버 보안 침해사고를 야기할 수 있다. 이에 본 논문에서는 원전 사이버 보안 취약점 규제 요건과 기존 취약점 스캐너의 특징 및 이들이 지닌 요건들을 분석하였고, 상용 및 무료 취약점 스캐너를 조사 하였다. 제안된 적용 방안을 바탕으로 취약점 스캐너를 원전에 적용할 시 원전의 네트워크 보안 취약점 점검 효율성을 향상시킬 수 있을 것으로 판단된다.

• 한국재난정보학회 논문집
• /
• 제18권2호
• /
• pp.252-260
• /
• 2022

연구목적: 기후변화 등으로 인해 자연재해의 빈도 및 강도가 증가하고 있어, 원자력발전소에 영향을 주는 외부사건이 발생할 수 있다. 원자력발전소는 자연재해, 인공재해 등 외부사건으로부터 안전해야 한다. 따라서 원자력발전소에 발생할 수 있는 외부사건을 식별하여야 하며, 원자력발전소에 큰 영향을 줄 수 있는 외부사건을 선별하여야 한다. 본 연구에서는 외부사건을 식별 및 선별하는 방법의 연구동향을 소개한다. 연구방법: 원자력발전소의 확률론적 안전성 평가를 위한 외부사건의 식별 및 선별에 관한 문헌조사를 실시하였다. 또한 국내외 외부사건의 식별 및 선별에 관한 규정을 조사하였다. 연구결과: 원자력발전소의 외부사건 영향분석의 비용을 최소화하고자 외부사건을 식별 및 선별하는 연구가 이루어지고 있다. 각 연구는 관점에 따라 차이를 보이지만 공통적으로 식별과정에서는 원자력발전소 부지에서 발생할 수 있는 모든 사건을 식별하고자 하며, 선별과정에서는 정성적 기준과 정량적 기준을 바탕으로 외부사건을 선별한다. 결론:기후변화 등으로 인하여 자연재해의 강도가 변화하고 있어, 원자력발전소에 영향을 주는 외부사건을 식별 및 선별하는 과정이 중요해지고 있다. 따라서 본 논문에서는 외부사건을 식별과 선별하는 방법에 대해 조사하여 정리하였다. 국내의 경우 원자력발전소의 확률론적 안전성 평가를 위한 외부사건의 식별과 선별에 관한 연구가 미미한 실정이다. 또한 외부사건 정량적 선별과정에서 수행하는 '경계분석'과 '명백히 보수적인 분석' 방법에 관한 연구가 필요할 것으로 보인다.